事故后安全壳内环境条件计算分析

以M 310＋型核电厂为例，计算分析了设计基准事故以及严重事故后安全壳内压力、温度环境条件。对核电厂设计基准事故和严重事故分析分别采用了法国的安全壳热工水力计算分析程序PAREO和一体化严重事故分析程序MAAP。计算分析给出了设计基准事故和严重事故下安全壳压力、大气温度和露点温度的峰值随时间变化曲线。计算结果表明设计基准事故和严重事故后，安全壳压力峰值工况均以MSLB为始发事故；设计基准事故后安全壳压力峰值为0.511 8 MPa，严重事故后安全壳压力峰值为0.602 MPa。

Computational Analysis of Environment Condition Inside Containment After Accident

The pressure and tempereature inside containment after both design basis accidents and severe accidents are calculated and anaylzed based on M 310+ NPP. Design basis accidents are calculated by French containment thermal hydraulic analysis code PAREO and severe accidents are calculated by integrated severe accident analysis code MAAP. The containment peak pressure, atomosphere and dew peak temperature of desigan basis accident and severe accident are calculated and shown. The results show that both design basis and severe accidents containment peak pressure conditions are induced by MSLB accident, that the peak containment pressure after design basis accidents is 0.511 8 MPa and after severe accidents is 0.602 MPa.